Testing of tungsten powder as a significant nuclear fusion reactor waste

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F23%3AN0000169" target="_blank" >RIV/26722445:_____/23:N0000169 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Testing of tungsten powder as a significant nuclear fusion reactor waste

Popis výsledku v původním jazyce

The inner surface of the fusion tokamak is impacted by various factors. For example, kinetic energy of the incidental neutral particles and their interaction with construction and functional materials have to be considered including the effect of radiation, high heat and electromagnetic loads inducing significant thermal and mechanical stresses as well as combination and synergy of all these phenomena. All these processes and phenomena changes the system’s entropy locally. Moreover, release of particles of various sizes from atomic, sizes through clusters of atoms to grains and larger compact units are being observed. Normal operation of the nuclear fusion device causes wear of the very durable tungsten armor in the reactor. Due to this process tungsten particles of different sizes are released. The liberated tungsten is usually tritiated. In the form of dust, it is removed from the reactor and becomes waste material. This valuable material should be separated from radioactive tritium and recycled. The goal of the paper is to introduce possibility of tungsten dust particles recycling. Various alternatives will be tested through MSO (Molten Salt Oxidation) technology or alternatively by induction heating and by induction melting or their combination. During tailored sintering processes, the green compacts will be densified to a degree that is sufficient for subsequent thermomechanical processing. Sintering of tungsten is commonly carried out between 2000 and 3000 °C under flowing hydrogen, or in a vacuum at similar temperatures, either by direct sintering (self-resistance heating) or indirect sintering (resistance element heating systems). The testing will be performed in vacuum chamber in increasing temperature. The samples will be further examined for determining diffusible hydrogen volume. Based on our results the decision about possible recycling tungsten dust particles will be taken. Poster at ICFRM-21.

Název v anglickém jazyce

Testing of tungsten powder as a significant nuclear fusion reactor waste

Popis výsledku anglicky

The inner surface of the fusion tokamak is impacted by various factors. For example, kinetic energy of the incidental neutral particles and their interaction with construction and functional materials have to be considered including the effect of radiation, high heat and electromagnetic loads inducing significant thermal and mechanical stresses as well as combination and synergy of all these phenomena. All these processes and phenomena changes the system’s entropy locally. Moreover, release of particles of various sizes from atomic, sizes through clusters of atoms to grains and larger compact units are being observed. Normal operation of the nuclear fusion device causes wear of the very durable tungsten armor in the reactor. Due to this process tungsten particles of different sizes are released. The liberated tungsten is usually tritiated. In the form of dust, it is removed from the reactor and becomes waste material. This valuable material should be separated from radioactive tritium and recycled. The goal of the paper is to introduce possibility of tungsten dust particles recycling. Various alternatives will be tested through MSO (Molten Salt Oxidation) technology or alternatively by induction heating and by induction melting or their combination. During tailored sintering processes, the green compacts will be densified to a degree that is sufficient for subsequent thermomechanical processing. Sintering of tungsten is commonly carried out between 2000 and 3000 °C under flowing hydrogen, or in a vacuum at similar temperatures, either by direct sintering (self-resistance heating) or indirect sintering (resistance element heating systems). The testing will be performed in vacuum chamber in increasing temperature. The samples will be further examined for determining diffusible hydrogen volume. Based on our results the decision about possible recycling tungsten dust particles will be taken. Poster at ICFRM-21.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

10305 - Fluids and plasma physics (including surface physics)

Projekt

<a href="/cs/project/9D22001" target="_blank" >9D22001: Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2023

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů